Low cycle fatigue behavior of T91 ferritic-martensitic steel hollow specimen in oxygen saturated lead–bismuth eutectic at 200 ∼ 450 °C

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-05-29 DOI:10.1016/j.nucengdes.2025.114185

Jianhua Ding , Jibo Tan , Ziyu Zhang , Xinqiang Wu , Xiang Wang , Wei Ke

引用次数: 0

Abstract

The low cycle fatigue behavior of T91 ferritic-martensitic steel hollow specimens were investigated in air and with oxygen saturated lead–bismuth eutectic (LBE) filled at 200 ∼ 450 °C. A clear fatigue endurance “trough” was observed with LBE-filled hollow specimens at 300 ∼ 350 °C, while the fatigue lives in air at different temperatures are comparable. The fracture surfaces with LBE-filled at 200 ∼ 350 °C were characterized by quasi-cleavage cracking, which indicates the occurrence of liquid metal embrittlement. By contrast, oxide scale on surface with LBE-filled at 400 ∼ 450 °C inhibited fatigue crack initiation. The fatigue crack initiation mechanisms at different temperatures are discussed.

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T91铁素体-马氏体钢空心试样在200 ~ 450°C氧饱和铅铋共晶中的低周疲劳行为

研究了T91铁素体-马氏体钢空心试样在空气中和充入氧饱和铅铋共晶（LBE）的200 ~ 450℃低周疲劳行为。填充lbe的空心试样在300 ~ 350℃时出现了明显的疲劳耐久性“槽”，而不同温度下的空气疲劳寿命具有可比性。在200 ~ 350℃时，填充lbe的断口表面出现准解理裂纹，表明发生了液态金属脆化。相比之下，在400 ~ 450°C时，lbe填充表面的氧化皮抑制了疲劳裂纹的萌生。讨论了不同温度下的疲劳裂纹萌生机制。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.